Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions
•ASTEC code calculations have been performed, within the first phase of reactor calculations of R2CA project (task 2.3).•LOCA DBA and DEC-A scenarios have been simulated.•Two cases have been considered for each scenario, characterized by some differences on initial/boundary conditions, accident mana...
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Veröffentlicht in: | Annals of nuclear energy 2024-08, Vol.203, p.110503, Article 110503 |
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Format: | Artikel |
Sprache: | eng |
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